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DNB and Void Fraction TRACE Model Validation with PSBT Experiments
dc.contributor | Kozlowski, Tomasz |
dc.contributor.author | Jara Heredia, Daniel |
dc.date.accessioned | 2012-03-13T10:02:55Z |
dc.date.available | 2012-03-13T10:02:55Z |
dc.date.issued | 2010 |
dc.identifier.uri | http://hdl.handle.net/2099.1/14686 |
dc.description.abstract | The aim of the thesis is the assessment and validation of numerical models for the prediction of detailed subchannel distribution and departure from nucleate boiling (DNB) to a full scale data on a prototypical PWR rod bundle. To carry out this goal the participant will used TRACE, a software designed by the United State Nuclear Regulatoey Commision. The student should study implications on reactor design and safety analyses, propose changes/additions to reactor design and propose new experiments. The thesis is composed ny the following sections: - Introduction - Description of the Facility - Description of the Method - Description of the Model - Results - Conclusions |
dc.language.iso | eng |
dc.publisher | Universitat Politècnica de Catalunya |
dc.publisher | Kungliga Tecniska Högskolan |
dc.subject | Àrees temàtiques de la UPC::Energies::Energia nuclear |
dc.subject.lcsh | Nuclear reactors |
dc.title | DNB and Void Fraction TRACE Model Validation with PSBT Experiments |
dc.type | Master thesis (pre-Bologna period) |
dc.subject.lemac | Reactors nuclears |
dc.rights.access | Open Access |
dc.audience.educationlevel | Estudis de primer/segon cicle |
dc.audience.mediator | Escola Tècnica Superior d'Enginyeria Industrial de Barcelona |
dc.audience.degree | ENGINYERIA INDUSTRIAL (Pla 1994) |
dc.description.mobility | Outgoing |